A possible divertor combined the advantages of supper-X and snowflake for CFETR/DEMO
Description
Full text: The experimental and modeling have shown that the advanced snowflake divertor can well mitigate heat flux loading onto target surfaces due to the smaller perpendicular incident angle and larger magnetic expansion compared with conventional divertor. But, the large magnetic expansion of snowflake may lead to a serious problem of particle exhaust, which results in the core plasma density out of control. In order to well control particle flux, we propose a possible divertor, which combines the advantages of supper-X and snowflake, including long leg, large magnetic expansion, closed contracture and small perpendicular incident angle. In this work, we will employ the authoritative edge plasma code SOLPS-ITER to evaluate the control capacity of particle and heat flux for this divertor. The primarily modeling results from SOLPS-ITER show that the carbon impurity and recycling particles can well be screened in outer divertor region accompanying with a large quantity of radiation loss power. Moreover, the neutral pressure is very high near target region due to the good screening, so that the neutral recycling and impurity particles can be removed by the pumping system. This possible divertor not only can well control heat flux, but also remove the partial impurity and recycling particle to control particle by pumping. Such a divertor may potentially provide a power and particle handling solution for long pulse advanced tokamaks. (author)
Additional details
Identifiers
Publishing Information
- Imprint Title
- Third IAEA Technical Meeting on Divertor Concepts. Report of Abstracts
- Imprint Pagination
- 68 p.
- Journal Page Range
- p. 2-3
- Report number
- INIS-XA--21M2087
Conference
- Title
- 3. IAEA Technical Meeting on Divertor Concepts
- Acronym
- DC 2019
- Dates
- 4-7 Nov 2019
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 52124359
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S71: CLASSICAL AND QUANTUM MECHANICS, GENERAL PHYSICS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CAPACITY; CARBON; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; DIVERTORS; HEAT FLUX; IMPURITIES; ITER TOKAMAK; PLASMA DENSITY; PULSES; PUMPING; SURFACES
- Descriptors DEC
- CLOSED PLASMA DEVICES; ELEMENTS; EVALUATION; NONMETALS; SIMULATION; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS
Optional Information
- Notes
- 5 refs.